Published May 2001 | Version v1
Miscellaneous

Analyses of reactor coolant flow rate decrease events using the KEPRI methodology

  • 1. KEPRI, Taejon (Korea, Republic of)

Description

KEPRI is developing the in-house methodology for non-LOCA safety analyses based on the codes and methodologies of vendors and EPRI. To verify the feasibility of the methodology, reactor coolant flow rate decrease events have been analyzed at the standpoint of RCS pressure. Furthermore, to assess the important parameters to RCS pressure, the sensitivity analyses have been carried out over some parameters such as reactivity feedback, reactor coolant temperature, and reactor coolant pressure. The results of these analyses have similar trends comparing with those of FSAR 15

Part of:
Proceedings of the Korean Nuclear Society spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting
Imprint Pagination
[ONE CDROM]
Journal Page Range
[14 p.]

Conference

Title
2001 spring meeting of the Korean Nuclear Society
Dates
24-25 May 2001
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33040457
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLANTS; EPRI; FEASIBILITY STUDIES; FEEDBACK; FLOW RATE; KOREAN ORGANIZATIONS; R CODES; SAFETY ANALYSIS; SENSITIVITY ANALYSIS
Descriptors DEC
COMPUTER CODES; NATIONAL ORGANIZATIONS

Optional Information

Notes
9 refs, 16 figs, 6 tabs